Tritium process applications using SAES getters for purification and collection from inert gas streams
- Idaho National Engineering Lab., Idaho Falls, ID (United States)
- Los Alamos National Lab., NM (United States)
A zirconium alloy getter-based tritium monitoring and collection system has been designed, built, and subsequently operated for three years at the Idaho National Engineering Laboratory. The system is automated to provide separation of tritium from {sup 41}Ar, collection of tritium on an hourly basis, unloading of getters for on-line tritium measurement via an ion chamber, and recollection of tritium on removable getters for daily assay in the laboratory. Three different SAES Getters alloys are employed to purify the gas stream (St 909), and separate the tritium from {sup 41}Ar and collect the tritium for measurement (St 727 and St 707). This system has demonstrated on-line tritium measurements as low as 20 {mu}Ci per sample with typical decontamination factors from {sup 41}Ar of 10{sup 7}. In addition, laboratory studies aimed at the recovery of tritium from graphitic targets have demonstrated further process applications for these getters. Prototypical gas cooled reactor targets, containing encapsulated {sup 6}Li, were irradiated at the Advanced Test Reactor at this laboratory. Samples were then heated to high temperatures to allow diffusive release of the tritium into a flowing helium stream. St 909 purifier and St 727 collector getters have been employed to demonstrate an efficient tritium recovery process. 14 refs., 4 figs., 1 tab.
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 219728
- Report Number(s):
- CONF-930937-; ISSN 0748-1896; TRN: 96:010805
- Journal Information:
- Fusion Technology, Vol. 27, Issue 2T; Conference: Course and workshop on tritium technology for fusion reactors, Varenna (Italy), 6-14 Sep 1993; Other Information: PBD: Mar 1995
- Country of Publication:
- United States
- Language:
- English
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